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Warsaw, Poland

Goniche M.,French Atomic Energy Commission | Jacquet P.,Culham Center for Fusion Energy | Van Eester D.,Laboratory for Plasma Physics Brusells | Bobkov V.,Max Planck Institute for Plasma Physics (Garching) | And 15 more authors.
Journal of Nuclear Materials | Year: 2015

Recent JET-ILW [1,2] experiments reiterated the importance of tuning the plasma fuelling in order to optimize ion cyclotron resonance frequency (ICRF) heating in high power H-mode discharges. By fuelling the plasma from gas injection modules (GIMs) located in the mid-plane and on the top of the machine instead of adopting the more standardly used divertor GIMs, a considerable increase of the ICRF antenna coupling resistances was achieved with moderate gas injection rates (<1.5 × 1022 e/s). This effect is explained by an increase of the scrape-off-layer density in front of the antennas when mid-plane and top fuelling is used. By distributing the gas injection to optimize the coupling of all ICRF antenna arrays simultaneously, a substantial increase in the ICRF power capability and reliability was attained. Although similar core/pedestal plasma properties were observed for the different injection cases, the experiments indicate that the RF-induced impurity sources are reduced when switching from divertor to main chamber gas injection. © 2014 Elsevier B.V. Source


Batani D.,French Atomic Energy Commission | Batani D.,University of Milan Bicocca | Koenig M.,Ecole Polytechnique - Palaiseau | Baton S.,Ecole Polytechnique - Palaiseau | And 32 more authors.
Proceedings of SPIE - The International Society for Optical Engineering | Year: 2011

This paper presents the goals and some of the results of experiments conducted within the Working Package 10 (Fusion Experimental Programme) of the HiPER Project. These experiments concern the study of the physics connected to "Advanced Ignition Schemes", i.e. the Fast Ignition and the Shock Ignition Approaches to Inertial Fusion. Such schemes are aimed at achieving a higher gain, as compared to the classical approach which is used in NIF, as required for future reactors, and making fusion possible with smaller facilities. In particular, a series of experiments related to Fast Ignition were performed at the RAL (UK) and LULI (France) Laboratories and were addressed to study the propagation of fast electrons (created by a short-pulse ultra-high-intensity beam) in compressed matter, created either by cylindrical implosions or by compression of planar targets by (planar) laser-driven shock waves. A more recent experiment was performed at PALS and investigated the laser-plasma coupling in the 1016 W/cm2 intensity regime of interest for Shock Ignition. © 2011 SPIE. Source


Batani D.,French Atomic Energy Commission | Koenig M.,Ecole Polytechnique - Palaiseau | Baton S.,Ecole Polytechnique - Palaiseau | Perez F.,Ecole Polytechnique - Palaiseau | And 28 more authors.
Plasma Physics and Controlled Fusion | Year: 2011

This paper presents the goals and some of the results of experiments conducted within the Working Package 10 (Fusion Experimental Programme) of the HiPER Project. These experiments concern the study of the physics connected to 'advanced ignition schemes', i.e. the fast ignition and the shock ignition approaches to inertial fusion. Such schemes are aimed at achieving a higher gain, as compared with the classical approach which is used in NIF, as required for future reactors, and make fusion possible with smaller facilities. In particular, a series of experiments related to fast ignition were performed at the RAL (UK) and LULI (France) Laboratories and studied the propagation of fast electrons (created by a short-pulse ultra-high-intensity beam) in compressed matter, created either by cylindrical implosions or by compression of planar targets by (planar) laser-driven shock waves. A more recent experiment was performed at PALS and investigated the laser-plasma coupling in the 10 16 W cm -2 intensity regime of interest for shock ignition. © 2011 IOP Publishing Ltd. Source


Krauz V.,RAS Research Center Kurchatov Institute | Mitrofanov K.,SRC RF TRINITI | Scholz M.,IPPLM | Paduch M.,IPPLM | And 3 more authors.
Plasma Physics and Controlled Fusion | Year: 2012

The results of studies of the plasma-current sheath structure on the PF-1000 facility in the stage close to the instant of pinch formation are presented. The measurements were performed using various modifications of the calibrated magnetic probes. Studies of the influence of the probe shape and dimensions on the measurements accuracy were done. The current flowing in the converging sheath at a distance of 40mm from the axis of the facility electrodes was measured. In the optimal operating modes, this current is equal to the total discharge current, which indicates the high efficiency of current transportation toward the axis. In such shots a compact high-quality sheath forms with shock wave in front of the magnetic piston. It is shown that the neutron yield depends on the current compressed onto the axis. This dependence agrees well with the known scaling, YnI ∼ 4. The use of the total discharge current in constructing the current scaling, especially for facilities with a large stored energy, is unjustified. © 2012 IOP Publishing Ltd. Source


Lerche E.,Laboratory for Plasma Physics Brusells | Lerche E.,EURATOM | Lerche E.,Culham Center for Fusion Energy | Goniche M.,French Atomic Energy Commission | And 59 more authors.
Nuclear Fusion | Year: 2016

Ion cyclotron resonance frequency (ICRF) heating has been an essential component in the development of high power H-mode scenarios in the Jet European Torus ITER-like wall (JET-ILW). The ICRF performance was improved by enhancing the antenna-plasma coupling with dedicated main chamber gas injection, including the preliminary minimization of RF-induced plasma-wall interactions, while the RF heating scenarios where optimized for core impurity screening in terms of the ion cyclotron resonance position and the minority hydrogen concentration. The impact of ICRF heating on core impurity content in a variety of 2.5 MA JET-ILW H-mode plasmas will be presented, and the steps that were taken for optimizing ICRF heating in these experiments will be reviewed. © 2016 EURATOM. Source

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